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NUREG-1537, Part 2 - NRC

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Revew Procedures<br />

AUXLARY SYSmEm<br />

The reviewer should evaluate the five items listed at the beginning of Chapter 9 of<br />

the format and content guide for auxiliary systems and facilities that possess or use<br />

byproduct material produced in the reactor, source material, or special nuclear<br />

material, as allowed by the 10 CFR <strong>Part</strong> 50 license.<br />

The reviewer should compare the design bases for systems and procedures with<br />

the requirements developed in other chapters of the SAR, especially Chapters 11<br />

and 12, "Conduct of Operations"; should evaluate the design features against<br />

experience with possession and use of radioactive materials at other facilities and<br />

laboratories; and evaluate agreement with the acceptance criteria.<br />

An important aspect of the control and use of this material is found in operations<br />

and health physics procedures. Although review of the actual procedures is not<br />

necessary, the reviewer should examine the basis for the procedures and the<br />

method for review and approval of facility procedures described in Chapter 12 of<br />

the SAR. In some cases, the reviewer may audit selected procedures as part of the<br />

review. -Normally, inspectors selectively review procedures as part of the<br />

construction and startup inspection process or as part of the ongoing inspection<br />

program for existing facilities.<br />

Evaluafion Finings<br />

This section of the SAR should contain sufficient information' to support thefollowing<br />

types of conclusions, iich willl be included in the stafs'safety"<br />

evaluation report:<br />

Auxiliary facilities and systems are designed for the possession and use of<br />

byproduct materials produced by the reactor and (if applicable) source and<br />

special nuclear material. The design bases include limits onrpotential<br />

personnel exposures that are in compliance with 10 CFR <strong>Part</strong> 20 and are<br />

consistent with the facility ALARA program, as described in'Chapter 11. '<br />

* To ensure that radiation exposures are acceptably limited, the design<br />

features and license conditions specify upper limits on source strengths of<br />

radionuclides authorized for possession or use in the auxiliary facilities<br />

under the 10 CFR <strong>Part</strong> 50 license. The applicant has described the<br />

authorized spaces for use of the material.<br />

* Design features and procedures provide reasonable assurance that<br />

uncontrolled release of radioactive material to the unrestricted environment<br />

will not occur.<br />

- RE;'. 0,2196 9-13 STANDARD REVIEW PLAN<br />

,. . REt. 0, 2/96 -- 9-13 .-~ - .. STANDARDREv2wPLAN

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